Plasma shape optimization for EAST tokamak using orthogonal method

doi:10.1088/1674-1056/28/1/015201

中国物理B ›› 2019, Vol. 28 ›› Issue (1): 15201-015201.doi: 10.1088/1674-1056/28/1/015201

• PHYSICS OF GASES, PLASMAS, AND ELECTRIC DISCHARGES • 上一篇下一篇

Plasma shape optimization for EAST tokamak using orthogonal method

Yuan-Yang Chen(陈远洋), Xiao-Hua Bao(鲍晓华), Peng Fu(傅鹏), Ge Gao(高格)

1 School of Electrical Engineering and Automation, Hefei University of Technology, Hefei 230000, China;
2 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230000, China

收稿日期:2018-08-23 修回日期:2018-10-26 出版日期:2019-01-05 发布日期:2019-01-05
通讯作者: Xiao-Hua Bao E-mail:sukz@ustc.edu.cn
基金资助:
Project supported by the National Natural Science Foundation of China (Grant No. 51677051) and the Institute of Plasma Physics, Chinese Academy of Sciences.

Plasma shape optimization for EAST tokamak using orthogonal method

Yuan-Yang Chen(陈远洋)¹, Xiao-Hua Bao(鲍晓华)¹, Peng Fu(傅鹏)², Ge Gao(高格)²

1 School of Electrical Engineering and Automation, Hefei University of Technology, Hefei 230000, China;
2 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230000, China

Received:2018-08-23 Revised:2018-10-26 Online:2019-01-05 Published:2019-01-05
Contact: Xiao-Hua Bao E-mail:sukz@ustc.edu.cn
Supported by:
Project supported by the National Natural Science Foundation of China (Grant No. 51677051) and the Institute of Plasma Physics, Chinese Academy of Sciences.

摘要/Abstract

摘要：

It is necessary to reduce the currents of poloidal field (PF) coils as small as possible, during the static equilibrium design procedure of Experimental Advanced Superconductive Tokamak (EAST). The quasi-snowflake (QSF) divertor configuration is studied in this paper. Starting from a standard QSF plasma equilibrium, a new QSF equilibrium with 300 kA total plasma current is designed. In order to reduce the currents of PF6 and PF14, the influence of plasma shape on PF coil current distribution is analyzed. A fixed boundary equilibrium solver based on a non-rigid plasma model is used to calculate the flux distribution and PF coil current distribution. Then the plasma shape parameters are studied by the orthogonal method. According to the result, the plasma shape is redefined, and the calculated equilibrium shows that the currents of PF6 and PF14 are reduced by 3.592 kA and 2.773 kA, respectively.

关键词: EAST, plasma shape, orthogonal method, plasma equilibrium calculation

Abstract:

Key words: EAST, plasma shape, orthogonal method, plasma equilibrium calculation

中图分类号: (Magnetic confinement and equilibrium)

52.55.-s

52.65.-y (Plasma simulation)

陈远洋, 鲍晓华, 傅鹏, 高格. Plasma shape optimization for EAST tokamak using orthogonal method[J]. 中国物理B, 2019, 28(1): 15201-015201.

Yuan-Yang Chen(陈远洋), Xiao-Hua Bao(鲍晓华), Peng Fu(傅鹏), Ge Gao(高格). Plasma shape optimization for EAST tokamak using orthogonal method[J]. Chin. Phys. B, 2019, 28(1): 15201-015201.

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Plasma shape optimization for EAST tokamak using orthogonal method

Plasma shape optimization for EAST tokamak using orthogonal method

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